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Category:CORRESPONDENCE-LETTERS
MONTHYEARVPN-084-99, Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided1999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211Q3281999-09-0909 September 1999 Forwards Insp Rept 50-344/99-06 on 990630-0701,21 & 0408-08. No Violations Noted.Insp Conducted to Review Decommissioning Activities Underway at Trojan Site & to Accompany Shipment of Reactor Vessel to Hanford,Washington for Burial ML20211J2101999-08-30030 August 1999 Forwards Request for Addl Info Re Application for Approval of Proposed Corporate Merger of Pacificorp & Scottishpower VPN-074-99, Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20211A7131999-08-16016 August 1999 Forwards Environ Assessment & Finding of No Significant Impact to Application for Exemption & License Amend Dtd 980827.Proposed Exemption & License Amend Would Delete EP Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,app E ML20211B4091999-08-16016 August 1999 Forwards Environ Assessment & Finding No Significant Impact to Application for an Exemption & License Amend Dated 980129.Proposed Exemption & License Amend Would Delete Security Plan Requirements of 10CFR50.54(p) & 10CFR73.55 VPN-067-99, Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 2451999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20210H5971999-07-27027 July 1999 Forwards Notice of Consideration of Approval of Application Re Merger & Opportunity for Hearing.Notice Being Forwarded to Ofc of Fr for Publication ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications VPN-069-99, Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr1999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210A6401999-07-19019 July 1999 Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions VPN-061-99, Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.11999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209D6231999-07-0808 July 1999 Forwards RAI Re Licensee 980827 Request for Amend That Would Delete Number of License Conditions & TS Requirements That Would Be Implemented After All Sf Has Been Removed from 10CFR50 Licensed Area.Response Requested within 30 Days VPN-053-99, Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev1999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev VPN-056-99, Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee1999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee VPN-051-99, Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection1999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20207A2751999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl VPN-049-99, Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad1999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20206J7931999-05-0707 May 1999 Forwards Insp Repts 50-344/99-04 & 72-0017/99-02 on 990322- 25 & 29-0408.One Violations Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206J8681999-05-0707 May 1999 Forwards Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Insp Observed Work Activities Associated with Lifting of Reactor Vessel in Preparation for Removal & Shipment to Hanford Reservation for Burial ML20206H4331999-05-0505 May 1999 Forwards Amend 201 to License NPF-1 & Se.Amend Revises PDTSs by Deleting ISFSI Area,Revises Subsection 4.1.1,replaces Figure 4.1-1 with New Figure 4.1-1 & Adds New Page to Figure 4.1-1 to Reflect Access Control (ISFSI) Area ML20206N1571999-05-0404 May 1999 Forwards Util Quarterly Decommissioning Status Rept for First Quarter of 1999,IAW State of or Energy Facility Siting Council Order Approving Trojan Decommissioning Plan, ML20206E1731999-04-29029 April 1999 Informs That NRC Staff Has Performed an Acceptance Review of Trojan Nuclear Plant License Termination Plan,Submitted by ,To Determine Whether LTP Provides Adequate Info to Allow Staff to Conduct Detailed Review ML20206E0211999-04-28028 April 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re 970212 Application for Amend.Proposed Amend Would Revise Trojan Permanently Defueled TS to Delete ISFSI Area ML20206C9591999-04-23023 April 1999 Forwards Amend 200 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20206C9221999-04-23023 April 1999 Forwards Amend 199 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building VPN-031-99, Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR501999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205T5471999-04-20020 April 1999 Forwards Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted ML20205N9061999-04-13013 April 1999 Forwards Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted.Inspectors Examined Portions of Physical Security, Access Authorization & FFD Programs VPN-032-99, Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents1999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents VPN-027-99, Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.21999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 VPN-038-99, Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 21999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 VPN-036-99, Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage1999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage VPN-037-99, Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas1999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas VPN-007-99, Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc1999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc VPN-008-99, Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan1999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan VPN-030-99, Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars1999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars VPN-029-99, Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities1999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML18107A6911999-02-25025 February 1999 Responds to 990218 e-mail Re Listed Questions Concerning SFP Partial Draindown Analysis Info VPN-028-99, Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-06021999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 VPN-021-99, Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License1999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License VPN-012-99, Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr1999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr VPN-015-99, Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 9901181999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 VPN-013-99, Forwards Fitness for Duty Program Performance Data Rept for July-Dec 19981999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARVPN-084-99, Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided1999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl VPN-074-99, Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) VPN-067-99, Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 2451999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications VPN-069-99, Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr1999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr VPN-061-99, Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.11999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 VPN-053-99, Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev1999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev VPN-056-99, Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee1999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee VPN-051-99, Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection1999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp VPN-049-99, Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad1999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad VPN-031-99, Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR501999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 VPN-032-99, Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents1999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents VPN-027-99, Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.21999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 VPN-038-99, Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 21999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 VPN-036-99, Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage1999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage VPN-037-99, Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas1999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas VPN-007-99, Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc1999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc VPN-008-99, Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan1999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan VPN-030-99, Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars1999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars VPN-029-99, Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities1999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities VPN-028-99, Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-06021999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 VPN-021-99, Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License1999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License VPN-012-99, Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr1999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr VPN-015-99, Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 9901181999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 VPN-013-99, Forwards Fitness for Duty Program Performance Data Rept for July-Dec 19981999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20199J1661999-01-14014 January 1999 Submits Summary of ISFSI Lid Welding Demonstration to Be Held 990118-25.Dates & Days Are Tentative & Can Be Adjusted as Necesssary or as Required ML20199J0801999-01-12012 January 1999 Forwards Schedule for Trojan Nuclear Plant ISFSI pre-op Test,Per Request VPN-002-99, Forwards Rev 1 to PGE-1073 Tnp ISFSI Security Plan,As Result of 981208 Telcon with Nrc.Encl Withheld,Per 10CFR73.211999-01-0808 January 1999 Forwards Rev 1 to PGE-1073 Tnp ISFSI Security Plan,As Result of 981208 Telcon with Nrc.Encl Withheld,Per 10CFR73.21 VPN-001-99, Requests That Svc List for Delivery of Documents from NRC Be Updated,Per 981230 Telcon.Substitute for Listings of HR Pate & J Westvold,Submitted1999-01-0404 January 1999 Requests That Svc List for Delivery of Documents from NRC Be Updated,Per 981230 Telcon.Substitute for Listings of HR Pate & J Westvold,Submitted VPN-004-99, Forwards Rev 5 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Table 2.2-5 Is Revised to Depict Major Components Removed from Plant During 1998.Revs Are Denoted by Side Bars1999-01-0404 January 1999 Forwards Rev 5 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Table 2.2-5 Is Revised to Depict Major Components Removed from Plant During 1998.Revs Are Denoted by Side Bars VPN-080-98, Forwards Updated ISFSI Emergency Plan,Per 981123 & Discussion in Meeting with NRC on 981119.Description of Changes Encl1998-12-17017 December 1998 Forwards Updated ISFSI Emergency Plan,Per 981123 & Discussion in Meeting with NRC on 981119.Description of Changes Encl VPN-076-98, Forwards Final Rept of Matl Properties of Neutron Shielding Matl to Be Used in Trojan ISFSI & Test Repts That Verified Matl Properties1998-11-25025 November 1998 Forwards Final Rept of Matl Properties of Neutron Shielding Matl to Be Used in Trojan ISFSI & Test Repts That Verified Matl Properties VPN-077-98, Forwards Listed ISFSI Calculation Refs,Per 981110 Telcon1998-11-24024 November 1998 Forwards Listed ISFSI Calculation Refs,Per 981110 Telcon VPN-075-98, Informs That,Per Commitments Made in 981119 Meeting with Nrc,Rev to PGE-1075 Will Be Submitted No Later than 9812181998-11-23023 November 1998 Informs That,Per Commitments Made in 981119 Meeting with Nrc,Rev to PGE-1075 Will Be Submitted No Later than 981218 VPN-053-98, Forwards Rev 7 to Trojan Nuclear Plant Defueled Sar. Attachment to Ltr Includes Brief Description of Each Change Included in Rev1998-11-17017 November 1998 Forwards Rev 7 to Trojan Nuclear Plant Defueled Sar. Attachment to Ltr Includes Brief Description of Each Change Included in Rev VPN-059-98, Forwards Rev 51 to Trojan Nuclear Plant Security Plan.Rev Withheld,Per 10CFR73.211998-11-10010 November 1998 Forwards Rev 51 to Trojan Nuclear Plant Security Plan.Rev Withheld,Per 10CFR73.21 VPN-063-98, Forwards Amend 7 to PGE-1052, Quality-Related List Classification for Tnp. Amend Removes Ref to Several Clean Up Sys,Deletes Exemptions Allowed by Reg Guide 1.143 & Deletes Figures No Longer Required to Support Discussion1998-10-27027 October 1998 Forwards Amend 7 to PGE-1052, Quality-Related List Classification for Tnp. Amend Removes Ref to Several Clean Up Sys,Deletes Exemptions Allowed by Reg Guide 1.143 & Deletes Figures No Longer Required to Support Discussion VPN-061-98, Requests That Further Review of License Change Application LCA-238 Be Suspended as Result of Progress Made in Decommissioning,Installation of Natural Gas Pipe Line1998-10-14014 October 1998 Requests That Further Review of License Change Application LCA-238 Be Suspended as Result of Progress Made in Decommissioning,Installation of Natural Gas Pipe Line VPN-058-98, Forwards Amend 20 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Reflecting Revisions to Fire Protection Program Made During Decommissioning Activities1998-09-28028 September 1998 Forwards Amend 20 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Reflecting Revisions to Fire Protection Program Made During Decommissioning Activities VPN-057-98, Forwards Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan, Per Request That Util Submit Description of Measures to Be Taken to Ensure Safe Transport of Tnp Rv & Internals Package1998-09-21021 September 1998 Forwards Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan, Per Request That Util Submit Description of Measures to Be Taken to Ensure Safe Transport of Tnp Rv & Internals Package VPN-050-98, Provides Rev 2 to Poge, Trojan NPP Permanently Defueled TS Bases. Changes Identified in Revised Text by Side Bars1998-09-10010 September 1998 Provides Rev 2 to Poge, Trojan NPP Permanently Defueled TS Bases. Changes Identified in Revised Text by Side Bars VPN-051-98, Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers1998-09-10010 September 1998 Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers VPN-052-98, Forwards Figures & Tables Identifying Nodes Assigned for Trojan ISFSI Transfer Station Analysis,TI-056,Rev 11998-09-0909 September 1998 Forwards Figures & Tables Identifying Nodes Assigned for Trojan ISFSI Transfer Station Analysis,TI-056,Rev 1 VPN-014-98, Requests Exemption of Emergency Plan Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,App E Following Transfer of Spent Nuclear Fuel to ISFSI1998-08-27027 August 1998 Requests Exemption of Emergency Plan Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,App E Following Transfer of Spent Nuclear Fuel to ISFSI VPN-048-98, Forwards Description of Review Methodology & Summary of Results,Including List of Identified Variations from Guidance Contained in Std Review Plan,Per NUREG-15361998-08-25025 August 1998 Forwards Description of Review Methodology & Summary of Results,Including List of Identified Variations from Guidance Contained in Std Review Plan,Per NUREG-1536 VPN-041-98, Forwards Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant. Rev Reflects Administrative Changes That Continue to Meet Requirements of 10CFR50,App B1998-08-25025 August 1998 Forwards Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant. Rev Reflects Administrative Changes That Continue to Meet Requirements of 10CFR50,App B 1999-09-23
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6651990-09-21021 September 1990 Forwards Application for Amend to License NPF-1,consisting of License Change Application 203,Rev 1.Rev Reduces Scope of Previous Changes Re Tech Spec Table 3.6-1, Containment Isolation Valves ML20059J9691990-09-14014 September 1990 Forwards Estimates of Facility Operator Licensing, Requalification & Generic Fundamentals Exam Requirements for FY91-94,per Generic Ltr 90-07 ML20059J9841990-09-14014 September 1990 Responds to Re Violations Noted in Insp Rept 50-344/90-21.Corrective Action:Individual Employee Terminated on Day of Event ML20059J0321990-09-0707 September 1990 Requests That Six Listed Candidates Take PWR & Generic Fundamentals Exam to Be Administered on 901010 ML20059D8031990-08-31031 August 1990 Forwards Update on Actions for NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20059D2401990-08-30030 August 1990 Extends Commitment Date from 900831 to 901031 to Amend FSAR Per Util 900404 Response to Notice of Violation ML20059D0831990-08-30030 August 1990 Revises Response to Violations Noted in Insp Rept 50-344/90-02.License Document Change Request Correcting FSAR Discrepancy Noted in App A,Violation C Re Request for Design Change Initiated & Will Be Incorporated Into Amend 14 ML20059D5601990-08-28028 August 1990 Forwards Fitness for Duty Performance Rept for 900103-0630. Overall Positive Rate for All Testing Conducted at Plant from 900103-0630 Is 0.71% ML20059D3201990-08-28028 August 1990 Responds to Deficiencies Identified by FEMA During 891115 Emergency Preparedness Exercise at Plant.Corrective Actions: Procedures Revised to Prioritize Roadblocks & Clearly Define Roadblocks for 5-mile & 10-mile Locations ML20059C1741990-08-28028 August 1990 Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20058M7861990-08-0303 August 1990 Forwards Monthly Operating Rept for Jul 1990.W/o Encl ML20056A1551990-07-31031 July 1990 Forwards Updated Response to Address Maint/Surveillance Area of SALP for Period from Jan 1989 - Mar 1990.Overall Plant Performance During Period Acceptable & Found to Be Directed Toward Safe Operation ML20055J3421990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Plant,Per 10CFR50.75.Certifies That Finanical Assurance Utilizing Methodology as Listed Will Be Available to Decommission Plant ML20055G7131990-07-20020 July 1990 Comments on Operator Licensing Exams Administered on 900717 ML20055G7141990-07-19019 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Plant Has Four Rosemount Model 1153DD6 Differential Pressure Transmitters Installed to Associated Logics for Safety Injection ML20055F8791990-07-16016 July 1990 Forwards 1989 Annual Repts for Portland General Corp,Eugene Water & Electric Board & Pacific Power & Light Co ML20044B3191990-07-13013 July 1990 Forwards Application for Amend to License NPF-1,consisting of License Change Application 202,revising RCS Flow Requirements & Portions of Bases ML20055F8161990-07-13013 July 1990 Advises of New Addressee for Nrc/Util Correspondence ML20055F6911990-07-13013 July 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML20055F2441990-07-12012 July 1990 Forwards Response to SALP Evaluation for Jan 1989 - Mar 1990 Re Maint/Surveillance.Util Plans to Improve Performance in Areas of Operation Through Commitment of Support from Nuclear Div Mgt & Personal Involvement of Corporate Mgt ML20055F2961990-07-0606 July 1990 Forwards Addl Info Re ATWS Mitigating Sys Actuation Circuitry ML20055E3401990-07-0606 July 1990 Forwards Application for Renewal of Plant NPDES Permit ML20055E1751990-07-0606 July 1990 Provides Update to 891130 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Rev to Maint Procedure 12-4, Valve Air Actuators, to Include Maint Insp Completed in Apr 1990 ML20055E0241990-07-0606 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-344/90-11.Corrective Actions:Generic Issues That Contributed to Violation Will Be Discussed During Mgt Meetings & Quality Insp Supervisor Counseled ML20055E0281990-07-0606 July 1990 Informs That Actions Committed to in Util Re Replacement of Breaker During 1990 Refueling Outage & Provision of Rept Documenting Replacement of Breaker, Complete,Per NRC Bulletin 88-010 05000344/LER-1990-015, Forwards LER 90-015-00 Re Control Room Emergency Ventilation Sys Coolers Found Inadequately Sized to Maintain Design Basis Temp.Rept Submitted 2 Wks Beyond 30-day Requirement Due to Difficulties Encountered in Preparation1990-07-0202 July 1990 Forwards LER 90-015-00 Re Control Room Emergency Ventilation Sys Coolers Found Inadequately Sized to Maintain Design Basis Temp.Rept Submitted 2 Wks Beyond 30-day Requirement Due to Difficulties Encountered in Preparation ML20058K4891990-06-30030 June 1990 Discusses Reduced Min Measured RCS Flow for Plant.Encl Figure 3.2-3 & Evaluation Support Operation W/No Tech Spec Setpoint Changes ML20055D0411990-06-29029 June 1990 Discusses Design Verification Program Re Main Steam Support Structure.Extension of Completion Date for Project Justified Since Documentation,Not Mod of Main Steam Support Structure Is Reason for Delay ML20055D0441990-06-29029 June 1990 Advises That Response to Generic Ltr 90-04 Re Status of Generic Safety Issues at Facility Delayed from 900629 to 900713 ML20055D7091990-06-26026 June 1990 Forwards Steam Generator Tube Plugging Rept,Per Inservice Insp ML20044A0881990-06-22022 June 1990 Forwards Proprietary Results of Reevaluation of Addl Steam Generator Tubes for Vibration-Induced Fatigue, Per NRC 900530 Telcon Request to Document Scope of Review of NRC Bulletin 88-002.Results Withheld (Ref 10CFR2.790) ML20043H9171990-06-19019 June 1990 Forwards List of Refs & Tables Re Reactor Vessel Matls & Preservice Properties,Per 900327 Request ML20043G5841990-06-15015 June 1990 Informs That WR Robinson Has Succeeded CP Yundt as General Manager of Plant,Effective 900615 05000344/LER-1990-016, Forwards LER 90-016-00 Advising That Calibr of Main Steam Flow Instruments Did Not Include All Required Elements.W/O Encl1990-06-13013 June 1990 Forwards LER 90-016-00 Advising That Calibr of Main Steam Flow Instruments Did Not Include All Required Elements.W/O Encl ML20043F6951990-06-0404 June 1990 Forwards Completed Regulatory Impact Survey,In Response to Generic Ltr 90-01 Covering NRC Team Insps,Special Insps, Resident Special Insps,Routine Unannounced Insps & NRC Resident Insps ML20043C6711990-05-31031 May 1990 Informs NRC of Need to Revise Reg Guide 1.97 Commitment Re Installation of post-accident Neutron Flux Recording Device. Items 1 & 2 Completed During 1990 Refueling Outage ML20043A7731990-05-17017 May 1990 Responds to NRC Re Violations Noted in Insp Rept 50-344/90-06.Corrective Actions:Plant Setpoint Change Procedure Revised to Address Process from Initiation of Calculation to Incorporation Into Device Calibr ML20043B0281990-05-17017 May 1990 Informs of Actions Being Taken by Licensee to Assure Operability of ESF Electrical Equipment Under All Svc Water Sys Temp Conditions & Train outages.Long-term Corrective Actions & Schedules for Implementation Encl ML20043A9221990-05-15015 May 1990 Advises That Current Schedule for Const of Upgraded Control Room Emergency Ventilation Sys CB-1 Redundant Air Intake Dampers Delayed from 1990 Refueling Outage Until 1992 Refueling Outage ML20042G5441990-05-0909 May 1990 Forwards Rev to Commitment Dates Re Notice of Violations Associated W/Insp Rept 50-344/89-09,per NRC & LER Submitted on 900208.Changes Recommended to Mgt Sys Used to Assign & Track Commitments ML20042G0001990-05-0707 May 1990 Forwards Application for Amend to License NPF-1,consisting of License Change Application 199,revising Tech Spec 3.5.1, ECCS - Accumulators, to Delete Surveillance Requirement 4.5.1.d ML20042G0231990-05-0707 May 1990 Forwards Application for Amend to License NPF-1,consisting of License Change Application 200,clarifying Definition of Tech Spec 1.12, Core Alteration & Updating Use in Tech Spec 3.4.9, Containment Bldg Penetrations ML20042F9861990-05-0707 May 1990 Forwards Application for Amend to License NPF-1,consisting of License Change Application 197,revising Tech Spec 3.1.3.4 Re Shutdown Rod Insertion Limit to Fully Define Withdrawn Rods as More than 223 Steps ML20034C7431990-05-0202 May 1990 Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20042E7891990-04-25025 April 1990 Forwards Proprietary Topical Rept BAW-10178P, Mark-BW Thermal Hydraulic Applications for Trojan Nuclear Plant, for Review & Approval.Rept Withheld (Ref 10CFR2.790) ML20034B7401990-04-22022 April 1990 Forwards Application for Amend to License NPF-1,adding Exemption to Tech Spec 3.0.4, Applicability Into Tech Spec 3.7.6.1, Control Room Emergency Ventilation Sys ML20034B5701990-04-20020 April 1990 Forwards Notification of NPDES Noncompliance & NPDES Discharge Monitoring Rept for Mar 1990. Violations Involved Exceeding Limits for Biological Oxygen Demand in Sewage Treatment Plant Effluent on 900321 ML20034A9531990-04-18018 April 1990 Requests Exemption from Testing Requirements of 10CFR50,App J,Section III.D.2.b(i) for Containment Air Lock Door Equalizing Valves.Completion of Review Requested by 900510 in Order to Test Valves ML20034A8271990-04-17017 April 1990 Forwards Topical Rept BAW-10176, Mark-BW Reload Safety Analysis for Trojan Nuclear Unit. Rept Summarizes Analyses for non-LOCA Transients & Accidents.Approval of Rept Needed to Support Use of B&W Fuel for Cycle 14 & Beyond ML20042E2881990-04-13013 April 1990 Forwards Revised Response to NRC Re Violations Noted in Insp Rept 50-344/89-12.Corrective Actions: Comprehensive Review of Util Nuclear QA Procedures 116 & 120 Performed 1990-09-07
[Table view] |
Text
_.
. a Portland General Electric Corpsiy
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l David W. Cockfield Vice President, Nuclear April 28, 1989 Trojan Nuclear Plant Docket 50-344 License NPF-1 j 1
Director, Office of Enforcement U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l l Washington DC 20555
Dear Sir:
Reply to a Notice of Violation' Your letter of April 4, 1989 transmitted a Notice of Violation and Proposed Imposition of civil Penalty associated with Nuclear Regulatory Commission j (NRC) Inspection Report No. 50-344/88-46. Our response to the Notice of Vio2rtion is attached. Also attached is a check which provides full pay-ment for the imposed civil penalty of-$75,000.-
Sincerely, i
Attachments c: Mr. John B. Martin Regional Administrator, Region V <
U.S. Nuclear Regulatory Commission 3 Mr. William T. Dixon l State of Oregon i l
Department of Energy l Mr. R. C. Barr NRC Resident Inspector I Trojan Nuclear Plant ,
8905090013 890428 PDR O ADOCK 05000344 PDC ' I a sw senon sm eonwo oremn 9ra *pgk f)
.gtSW
_ _ - - _ - _ - - - _ _ _ _ _ _ _ - _ - _ - _ _ _ _ - _ _ - _ - - - _ _ _ __ a
, Trojen Nuclose Plant Docum:nt Control Dask
- . Docket 50-344 Attachment i License NPF-1 April 28, 1989 Page 1 of 7 REPLY TO NOTICE OF VIOLATION l
Applicable Regulations Title 10 to the Code of Federal Regulations, Part 50, (10 CFR 50), Appendix B, Criterion III, " Design Control," requires, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instruc tions . These measures shall include provisions to assure that appro-priate quality standards are specified and included in design documents and l
that deviations from such standards are controlled. Measures shall also be established for the selection and review for suitability of application of l materials, parts, equipment, and processes that are essential to the safety-l related functions of the structures, systems, and components.
10 CFR 50, Appendix B, Criterion IV, " Procurement Document Control," requires that measures be established to assure that applicable regulatory require-ments, design bases, or other requirements which are necessary to assure adequate quality are suitably included or referenced in the documents for procurement of material, equipment, and services. To the extent necessary, procurement documents shall require contractors or subcontractors to provide a quality assurance program consistent with the pertinent provisions of Appendix B.
10 CFR 50, Appendix B, Criterion X, " Inspection," requires, in part, that examinations, measurements, or tests of material or products processed shall be performed for each work operation where necessary to assure quality.
Violations contrary to the above, commercial-grade components at the Trojan Nuclear Plant were installed without adequately assuring their suitability for use in safety-related applications:
- 1. During the 1987 outage, in response to Maintenance Request (MR)
No. 87-4129, 14-inch Schedule 60 piping and fittings purchased from Liberty Equipment and weld metal purchased from Oxarc were installed inside Containment to replace eroded main feedwater system piping.
Portland General Electric Company (PGE) failed to assure the proper selection and review for suitability of application of these materials for this safety-related application. These materials were purchased commercial-grade without adequate audits to assure that the vendors
( fabricated the materials under a Quality Assurance (QA) program consis-tent with the pertinent requirements of 10 CFR 50, Appendix B, and with-out performing tests or examinations to assure the quality of these materials,
Trojan Nuclear Plant Document Control Desk
. . Docket 50-344 Attachment License NPF-1 April 28, 1989 Page 2 of 7
- 2. Between August 1987 and June 1988, a time-delay relay was installed per MR No. 87-5412. PGE failed to assure adequate design control for the proper selection and review for the commercial-grade purchase of the Agastat time-delay relay (Purchase Order (PO) No. NQ-04064-05] used in the diesel-driven auxiliary feedwater pump in that critical character-istics of the relay were not properly evaluated and specified.
- 3. Between May 2 and May 4, 1986, a pressure regulator valve was installed per MR No. 86-2180. PGE failed to assure adequate design control for the proper selection and review for the commercial-grade purchase of the pressure regulator valve (PO No. NQ-02468) used in the emergency diesel air start system in that critical characteristics of the valve were not properly evaluated and specified.
This is a severity Level III problem (Nupplement I).
REPLY TO VIOLATIONS 1. 2 AND 3 Portland General Electric Company acknowledges the violations.
- 1. REASON FOR THE VIOLATIONS:
These violations were the result of a deficient procurement process. The deficiencies were identified by the Nuclear Regulatory Commission (NRC) in 1985 and resulted in a Notice of Violation regarding commercial-grade items. Because of a lack of understanding of the requirements of 10 CFR 50, Appendix B, as they relate to the procurement process, the corrective actions taken by PGE as a result of the 1985 violation were ineffective.
In addition, a contributing factor to the violations was the fact that the Nuclear Quality Assurance Department (NQAD) became so involved with the formulation of the procurement process that they were unable to perform their intended function of providing critical and independent oversight of procurement activities.
- 2. CORRECTIVE STEPS TAKEN OR BEING TAKEN TO PREVENT FUTURE VIOLATIONS AND RESULTS ACHIEVED:
Effective November 28, 1988, PCE began requiring an engineering evalu-ation be completed prior to issuing a commercial-grade item for a safety-related application. PGE has also implemented a procurement policy that items purchased for safety-related applications will be purchased as basic components whenever feasible. When items for safety-related appli-cations are procured commercial-grade, the items will be dedicated as discussed below.
l
. Trojtn Nuclear Plant Docum:nt Control Dask
. - Docket 50-344 Attachment License NPF-1 April 28, 1989 Page 3 of 7 Revisions to the Procurement Process and Evaluation of Current Inventory l To ensure that all commercial-grade items intended for. safety-related applications are properly specified and accepted for use as basic compo-nents, two new temporary procedures were issued on December 29, 1988. l l \
Administrative Order (AO)-T-29, " Material Issue Control", provides l l instructions to control the issue of items for use in safety-related applications and supplements the current procedure for material control and identification. A0-T-30, " Material Engineering Evaluation", estab-lishes.the requirements, methods and processes for performing engineering evaluations of warehoused or purchased commercial-grade items prior to utilization in a safety-related application. The evaluation function is being performed by Nuclear Plant Engineering and includes determining the item's critical characteristics for its intended safety function, and identifying those attributes necessary for acceptance of the item as a basic component.
These procedures ensure that commercial-grade items currently in inven-tory, presently on order, and procured in the future meet all regulatory cnd industry requirements for their intended applications. The proco-dures also establish procurement requirements, including a verification inspection program for commercial-grade items, for all future procurement of standard inventory items.
The controls established by these two temporary procedures are being incorporated into Nuclear Division Procedures (NDP) 300-1 through 300-5, the Procurement Series. The revisions to the NDP-300 Series will be completed by June 30, 1989.
The evaluations of commercial-grade items utilize the dedication method-ology delineated in Electric Power Research Institute (EPRI) Docu-ment NP-5652, " Dedication of Commercial-Grade Items". The modifications to the EPRI guidelines for acceptance methods that are recommended in l Generic Letter 89-02, " Actions to Improve the Detection of Counterfeit l and Fraudulently Marketed Products", are incorporated in PGE's program.
, Acceptance of items is performed and implemented in accordance with the l EPRI guideline (with the noted exceptions) and Regulatory cuide 1.123,
" Quality Assurance Requirements for Control of Procurement of Items and l Services for Nuclear Power Plants". l This program has ensured that all commercial-grade items installed in l- safety-related applications after November 28, 1988 have had adequate review to establish that they are acceptable for the specific application.
i I
1
Trojan Nuclear Plant Document Control Dask )
- Docket 50-344 Attachment License NFF-1 April 28, 1989 Page 4 of 7 Evaluation of Installed Items To address commercial-grade items installed in safety-related applica-tions prior to November 28, 1988, an installed item evaluation was performed. j To support the preparation of the Justification for Continued Operation (JCO) for commercial-grade procurement issues (JCO 88-15) originally submitted on November 29, 1988 and revised on February 17, 1989, a review ,
of commercial-grade items issued from the warehouse between January 1986 ]
and November 1988 was performed to ensure functional adequacy of the ]
items. Subsequently, PGE has performed an additional review and evalu-ation of. installed items to verify and document the original review and more thoroughly address commercial-grade items installed in safety-related applications. This review and evaluation process is shown in ,
Figure 1.
The first step of ths effort was to perform a screening process of over 20,000 MRs issued between September 1, 1985 and December 1, 1988 to determine if commercial-grade items or materials were issued from the warehouse for environmental qualification (EQ), American Society of Mechanical Engineers (ASME)Section XI (Boiler and Pressure Vessel Code),
Standard Technical Specifications, or safety-related applications. This first step identified 3400 MRs that required a more detailed review.
The second step was to review these 3400 MRs in detail to identify those that performed safety-related work. Of the 3400 MRs, 2700 were identi-fled as performing safety-related work. These 2700 MRs were evaluated to identify items involving EQ, seismic qualification, and ASME Section XI pressure-retaining installations. Approximately 1200 of the 2700 safety-related MRs fall in this category. . These items will'be completely evaluated and dispositioned prior to restart from the 1989 refueling outage.
Commercial-grade items installed by the remaining 1500 MRs will be reviewed once the high-priority installations have been addressed and will be dispositioned by October 31, 1989. Startup and operation of Trojan prior to dispositioning these items is justified for the reasons stated in JCO 88-15.
The evaluation of each MR involves identifying the commercial-grade item (s) installed in a safety-related application. The commercial-grade items are dispositioned in one of three ways:
(1) The critical characteristics will be identified and verified, or (2) A determination will be made that the item neither provides a safety-related function nor does it affect the safety-related performance of other equipment, or
Trojan Nucicar Plcnt Docum:nt Control Dask l Docket 50-344 Attachment License NPF-1 April 28, 1989 Page 5 of 7 (3) A Nonconformance Report (NCR) will be prepared to either replace the item or justify continued operation with the item installed.
l To assist in performing the engineering evaluations, the installed item review, and the revisions to the procurement procedures, PGE contracted personnel experienced in material management. These individuals are I working with PGE employees to provide training in procurement require-ments and the commercial-grade dedication process. Their expertise and l industry-wide experience in the area of commercial-grade procurement has enabled PCE to develop a strong procurement program that meets all regu- i latory requirements. l Ouality Assurance Assessment r l To enable NQAD to independently assess the procurement process, the i responsibility for the procurement procedures was transferred to the Material Services Manager in December 1988.
NQAD has conducted three separate surveillance to assess the adequacy of the systematic review and evaluation of commercial-grade materials.
These surveillance covered the methodology used for preparation of the original JC0 88-15, the process for identifying MRs which installed com-mercial-grade materials in safety-related systems, and the evaluations of installed commercial-grade materials.
These surveillance have verified that the review and evaluation process is comprehensive and effective. Recommendations made by NOAD for improvements to work instructions were incorporated during the course of the third surveillance.
In addition, all evaluations performed by Nuclear Plant Engineering on commercial-grade items intended for safety-related applications are subject to independent review by NQAD personnel specifically assigned to thit. =ctivity, Corrective Steps to Address Specific Violations violation 1:
The commercial-grade items installed in the safety-related portion of the main feedwater system have been identified and a testing program has been established to demonstrate their acceptability for safety-related service. The scope of the testing program is described in our JC0 for Safety-Related Main Feedwater Piping (JCO 89-01) dated February 21, 1989. Testing will be completed prior to testart following the 1989 refueling outage.
i I
, Trojan Nuclear Plant Document Control Desk
- - Docket 50-344 Attachment License NPF-1 April 28, 1989 Page 6 of 7 Violation 2:
The commercial-grade time delay relay utilized for the diesel-driven auxiliary feedwater pump will be replaced with a fully qualified replace-ment prior to restart following the 1989 refueling outage.
Violation 3:
A commercial-grade itent evaluation will be performed for the pressure regulator valve installed in the emergency diesel generator air start system. The evaluation will include identification and verification of the valve's critical characteristics. This evaluation will be completed prior to restart from the 1989 refueling outage.
- 3. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED:
PGE's procurement process for commercial-grade items intended for safety-related applications is in full compliance with regulatory requirements.
The various portions of PGE's action to address other aspects of the commercial-grade process will be completed as stated above.
GAZ/SAB/PGN/mr 3024W.0489
l Trojan Nuclear Plant Document Control Desk
- Docket 50-344 April 28,1989 License NPF-1 Attachme- !
Page 7 of 7 REVIEW OF INSTALLED COMMERCIAL-GRADE ITEMS !
l Over 20,000 MR's issued between No F September 1,1985 and December 1, m Return '
1988 were reviewed to determine to storage if any parts with OA Level Codes C, C1,C2, or D were Installed in ASME Section XI pressure retaining, Safety-Related, EO, or Technical Specification applications YesT r
3400 MR's identified for further evaluation if Detailed review done to No F 700 MR's out '
determine if MR performed >t of scope ;
safety-related work Yes I P r '
2700 MR's for further evaluation ,
if MR's evaluated to No 1500 MR's recetve '
determine If E0, Seismic ; complete evaluation j or ASME Section XI pressure g by October 31,1989 ;
retalning application Yes Y lI 1. Critical characteristics of item F are identlfled and verified, or 1200 MR's receive '
complete evaluation p 2. Documented safety evaluation that prior to restart the item is not safety-related, or
- 3. NCR ls prepared to replace item or justify continued operation FIGURE 1
_ _ _ _ - _ _ _ _ _ -